Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 541-560 of 913
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Thermal–Hydraulic Design in the Transition Laminar–to–Turbulent Flow Regime
(The American Society of Mechanical Engineers (ASME), 2019)Difficulties are experienced during the thermal–hydraulic design of a nuclear reactor operating in the transition flow regime and are the result of the inability to accurately predict the heat transfer coefficient (HTC). ... -
Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code
(The American Society of Mechanical Engineers (ASME), 2019)DIONISIO is a computer code designed to simulate the behavior of one nuclear fuel rod during its permanence within the reactor. Starting from the power history and the external conditions to which the rod is subjected, the ... -
Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD
(The American Society of Mechanical Engineers (ASME), 2019)During operation of light water reactors, the Zircaloy fuel rod cladding is susceptible for hydrogen uptake. When the local solubility limit of hydrogen in Zircaloy is reached, additional hydrogen precipitates as zirconium ... -
Pyrolysis and High Performance Plasma Treatment Applied to Spent Ion Exchange Resins
(The American Society of Mechanical Engineers (ASME), 2019)Treatment and conditioning of spent ion exchange resins from nuclear facilities is a complex process that not only should contemplate obtaining a stable product suitable for long-term storage and/or disposal, but also have ... -
Special Section: Selected Papers From the 2018 International Youth Nuclear Congress
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Reviewer's Recognition
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A Study on Hydrogen Emission of Zirconium Hydride
(The American Society of Mechanical Engineers (ASME), 2019)The hydrogen emission of zirconium hydride at high temperature is a challenging issue for many researchers. The hydrogen emission content of zirconium hydride pins should be evaluated to confirm the application feasibility. ... -
Transport Mechanism of Steam Methane Reforming on Fixed Bed Catalyst Heated by High Temperature Helium for Hydrogen Production: A Computational Fluid Dynamics Investigation
(The American Society of Mechanical Engineers (ASME), 2019)In this study, we numerically evaluated the performance of a steam methane reforming (SMR) reactor heated using high-temperature helium for hydrogen production. The result showed that with an increase in the reactant gas ... -
Analyses of the Costs Associated With Very High Turbine Entry Temperatures in Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2019)Previous analyses of generation IV (GEN IV) helium gas turbine cycles indicated the possibility for high turbine entry temperatures (TETs) up to 1200 °C in order to improve cycle efficiency, using improved turbine blade ... -
Calibration of HPGe Detector Efficiencies With Self-Absorption Correction of Gas Sphere Sources
(The American Society of Mechanical Engineers (ASME), 2019)Several types of radioactive gases are released from the nuclear reactor. In order to measure the activity of such gases, it is necessary to calculate the accurate efficiency. Practically, efficiency calibration with gaseous ... -
Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver
(The American Society of Mechanical Engineers (ASME), 2019)Due to the recent high interest on in-vessel melt retention (IVR), development of detailed thermal and structural analysis tool, which can be used in a core-melt severe accident, is inevitable. Although RELAP/SCDAPSIM is ... -
Guided Waves as an Online Monitoring Technology for Long-Term Operation in Nuclear Power Plants: Experimental Results on a Steam Discharge Pipe
(The American Society of Mechanical Engineers (ASME), 2019)Guided wave (GW) testing is regularly used for finding defect locations through long-range screening using low-frequency waves (from 5 to 250 kHz). By using magnetostrictive sensors, some issues, which usually limit the ... -
Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding
(The American Society of Mechanical Engineers (ASME), 2019)In this study, based on the code Fuel ROd Behavior Analysis (FROBA), a thermal–mechanical analysis code initially developed for traditional UO2-Zr fuel elements by our research group, a modified version was developed to ... -
Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C
(The American Society of Mechanical Engineers (ASME), 2019)The choice of materials is of great concern in the construction of Gen IV supercritical water reactors (SCWR), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. A material's ... -
Evaluation of Interfacial and Permeation Leaks in Gaskets and Compression Packing
(The American Society of Mechanical Engineers (ASME), 2019)The quantities of leak rate through sealing systems are subjected to strict regulations because of the global concern on radiative materials. The maximum tolerated leak is becoming a design criterion in pressure vessel ... -
Obstructed View Factor Calculations for Multiple Obstructions in Closed Cavities
(The American Society of Mechanical Engineers (ASME), 2019)The inertial confinement fusion (ICF) program has been mainly concentrating on the indirect drive approach for the last three decades, due to relaxed requirements on driver-beam uniformity and reduced sensitivity to ... -
Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO2 as Working Fluid
(The American Society of Mechanical Engineers (ASME), 2019)In the case of an accident in a nuclear power plant with combined initiating events (loss of ultimate heat sink and station blackout), an additional heat removal system could transfer the decay heat from the core to an ... -
Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients
(The American Society of Mechanical Engineers (ASME), 2019)Transient performance of China supercritical water-cooled reactor (SCWR) with the rated electric power of 1000 MWel (CSR1000) core during some typical transients, such as control rod (CR) ejection and uncontrolled CR ... -
Predicting Leak Rate Through Valve Stem Packing in Nuclear Applications
(The American Society of Mechanical Engineers (ASME), 2019)Leaking valves have forced shutdown in many nuclear power plants. The myth of zero leakage or adequate sealing must give way to more realistic maximum leak rate criterion in design of nuclear bolted flange joints and valve ... -
New Exploration on TMSR: Redesign of the TMSR Lattice
(The American Society of Mechanical Engineers (ASME), 2019)Molten salt reactor (MSR) has been recognized as one of the next-generation nuclear power systems. Most MSR concepts are the variants evolved from the Oak Ridge National Laboratory (ORNL's) molten-salt breeder reactor ...